Waterford Unit 3 - 2009-10 - Final Written Exams. · RO 16 Tech Spec 3.8.2 RO 32 OP-902-009...

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Revision 1

NRC WRITTEN EXAM REFERENCE HANDOUT

RO/SRO Question Reference

RO 16 Tech Spec 3.8.2

RO 32 OP-902-009 Attachment 2E

RO 37 Tech Spec 3.3.1 & 3.3.2

RO 63 COLR Fig 3

RO 68 Drawing B424-707

SRO 1 OP-902-009 Appendix 1

SRO 5 Tech Spec 3.8.3.1

SRO 7 Tech Spec 3.1.3.1 & 3.1.3.6; COLR Fig 5

SRO 12 OP-902-009 Attachment 2A

SRO 16 OP-903-013 Attachment 10.3 (page 3)

SRO 23 EP-002-052 Attachment 7.2 & 7.3

U.S.N.R.C. site-Specific Written Examination Waterford 3

Reactor Operator

Page 1 of 75

Question 001 The following plant conditions exist:

The plant was operating at 100% power CEDMCS MG set B is tagged out Breaker 2A to 3A was inadvertently OPENED causing a loss of Bus 3A EDG ‘A’ is running Pressurizer level is 15% and slowly rising Pressurizer pressure is 2020 PSIA and slowly rising RCS temperature (Tcold) is 554º F and stable SG #1 and SG #2 pressures are 1020 PSIA and slowly lowering SG #1 and SG #2 levels are 7% & 9% NR respectfully and slowly rising Crew has diagnosed OP-902-001, Reactor Trip Recovery.

Which ONE of the following operator action(s) is required by procedure to address these plant conditions? (ASSUME all other equipment functioned per design.)

A. Direct NAO(s) to place DCT Sump pumps in operations per Appendix 20 AND raise EFW flow to restore SG levels to 50% - 70% NR.

B. Calculate a Shutdown Margin, AND raise EFW flow to restore SG levels to 50% - 70% NR.

C. Direct NAO(s) to place DCT Sump pumps in operations per Appendix 20 AND take MANUAL control of SBCS to lower RCS temperature to less than 550º F.

D. Calculate a Shutdown Margin, AND take MANUAL control of SBCS to lower RCS temperature to less than 550 ºF.


Reactor Operator

Page 2 of 75

Question 002 Which ONE of the following parameters would be expected to RISE immediately following a Pressurizer Steam Space break?

A. RCS Tcold B. Pressurizer level C. Pressurizer pressure D. Containment pressure


Reactor Operator

Page 3 of 75

Question 003 A Loss of RCS Coolant event (SBLOCA) has occurred in Containment. The plant was shutdown and a cooldown/depressurization is in progress. Containment temperature peaked at 185 °F. Which ONE of the following conditions would permit stopping one HPSI pump? [Assume ALL other required conditions are MET.] A. RCS subcooling is reading 26°F and stable B. Pressurizer level is indicating 5% and stable C. Steam Generator Levels are indicating:

SG#1 at 58% NR and stable SG#2 at 55% NR and slowly rising

D. RVLMS indicates Vessel Level Plenum at 60%


Reactor Operator

Page 4 of 75

Question 004 The ATC notes the following indications on RCP 1A:

• RCS pressure is 2250 PSIA • Middle Seal is 1250 PSIG • Upper Seal is 1180 PSIG • Vapor Seal is 45 PSIG

Which ONE of the following RCP 1A seals has failed or is degraded? A. Lower B. Vapor C. Upper D. Middle


Reactor Operator

Page 5 of 75

Question 005 With the plant operating at 100% power, which ONE of the following would cause a loss of Letdown flow?

A. Regen Heat Exchanger outlet temperature is 477 ºF B. Letdown Heat Exchanger outlet temperature is 148 ºF. C. VCT Inlet/Bypass Valve control switch left in BMS position. D. Letdown flow is 126 GPM with only one Charging Pump running.


Reactor Operator

Page 6 of 75


• Plant is in MODE 6 • Refueling Cavity level is 24 Feet above the Reactor Vessel Flange • Plant has been shutdown for 75 Hours • RCS temperature is 140 °F • Shutdown Cooling Train B is in service • LPSI Pump B trips and cannot be restarted • RCS temperature has risen to 142 °F

Which ONE of the following describes the MINIMUM total Shutdown Cooling flow, and the MAXIMUM RCS cooldown rate allowed by procedure?

A. 4000 GPM; 60 ºF/hr B. 4000 GPM; 100 ºF/hr C. 3000 GPM; 60 ºF/hr D. 3000 GPM; 100 ºF/hr


Reactor Operator

Page 7 of 75

Question 007 Following a valid CSAS signal, the operator can override this signal and close CS-125A, Containment Spray Header A Isolation valve, by taking the _________ to CLOSED. A. CP-8 control switch B. CP-8 control switch to OPEN, then back C. Aux Panel keyswitch for CS-125A to OVERRIDE, then take the CP-8 control switch D. Aux Panel keyswitch for CS-125A to OVERRIDE, then take the CP-8 control switch

to OPEN, then back


Reactor Operator

Page 8 of 75

Question 008 The crew has entered OP-901-120, Pressurizer Pressure Control Malfunction, following a loss of all Pressurizer heaters. Pressurizer Spray Controller has been adjusted to 0% and both spray valves are closed. Prior to shifting Pressurizer Level Setpoint source input to RTGB, a procedure NOTE states to maintain Pressurizer Level control constant.

Which ONE of the following statements describes the reason for this action?

A. Minimize stress on the Pressurizer Heaters B. Conserve Pressurizer inventory C. Raise Pressurizer enthalpy D. Lower RCS enthalpy


Reactor Operator

Page 9 of 75

Question 009 With the plant operating at 95% power, a large grid perturbation occurs. All 4 RCS low flow trip signals are generated, but NO Reactor Trip Circuit Breakers open. The ATC operator pushes the Reactor Trip push buttons on CP-2. Based on these actions, Reactor Trip Circuit Breakers __(1)__ should directly OPEN. If not, the ATC should push the DRTS push-buttons, which will OPEN the CEDMCS MG Set __(2)__.

(1) (2) A. 1, 4, 5, and 8 load contactors B. 2, 3, 6, and 7 load contactors C. 1, 4, 5, and 8 supply breakers D. 2, 3, 6, and 7 supply breakers


Reactor Operator

Page 10 of 75

Question 010 The following plant conditions exist.

Plant was operating at 100% power An RCS leak was identified. The crew diagnosed a Steam Generator Tube Rupture condition which required

a Reactor Trip. Following the reactor trip, the crew entered OP-902-007, Steam Generator Tube Rupture Recovery procedure.

Which ONE of the following recovery actions is intended to minimize RCS break flow to the Steam Generator?

A. Perform a rapid RCS cooldown to less than 520°F Thot. B. Isolate the most affected Steam Generator with RCS Thot less than 520°F. C. Depressurize the RCS to less than 945 PSIA and within 50 PSIA of affected SG

pressure. D. Cooldown the RCS to less than 350°F Thot or CET temperature using Steam

Bypass Control Valve.


Reactor Operator

Page 11 of 75


• The Plant was operating at 100% power when a Reactor Trip occurred • RCS Tcold is 539 °F and lowering • Containment pressure is 15.1 PSIA and stable • Pressurizer pressure is 2000 PSIA and slowly lowering • SG #1 level is 29% NR and slowly lowering • SG#1 pressure is 664 PSIA and lowering • SG#2 level is 38% NR and rising • SG#2 pressure is 700 PSIA and rising

Which ONE of the following signals should the operators verify has automatically actuated?

A. Safety Injection (SIAS) B. Main Steam Isolation (MSIS) C. Containment Spray (CSAS) D. Emergency Feedwater (EFAS)


Reactor Operator

Page 12 of 75


Plant was operating at 100% power when a loss of Main Feedwater occurred.

The crew performed a manual Reactor Trip and entered OP-902-000, Standard Post Trip Actions.

Which ONE of the following procedural requirements ensures a Steam Generator is removing heat from the core?

A. VERIFY RCS cold leg temperature slowly rising. B. VERIFY Moisture Separator Reheater Temperature Control Valves closed. C. CHECK at least one Steam Generator level is being restored to between 50% to

70% NR using Emergency Feedwater. D. CHECK Main Feedwater REG valves are closed and Startup Feedwater REG valves

are at least 20% open.


Reactor Operator

Page 13 of 75


Station Blackout has occurred

Crew is performing actions in OP-902-005, Station Blackout Recovery

The blackout is expected to last for greater than 1 hour

Which ONE of the following describes the strategy for alignment of electrical equipment during the Blackout recovery in accordance with OP-902-005?

Based on this condition, the crew must reduce unnecessary station loads… A. Within 30 minutes to ensure DC Batteries A & B meet their design coping times. B. Within 30 minutes to protect plant equipment from high temperature following a

loss of ventilation. C. Within 4 hours to ensure DC Batteries A & B meet their design coping times. D. Within 4 hours to protect plant equipment from high temperature following a loss of

ventilation.


Reactor Operator

Page 14 of 75

Question 014 The crew experienced a Loss of Offsite Power (LOOP) and entered OP-902-000, Standard Post Trip actions. All equipment responded per design.

Which ONE of the following describes the response of the Auxiliary Component Cooling system to these conditions?

A. ACCW pump ‘A’ will auto start B. ACCW Jockey pump ‘A’ will auto start C. ACC -126A(B) setpoint will go to 115º F D. Essential Chiller Supply/Return valves (ACC-112A/139A) will open


Reactor Operator

Page 15 of 75


A refueling outage is in progress.

The plant is in Mode 5 following completion of core alterations.

The ATC is adding PMU to the Volume Control Tank to bring RCS boron concentration from 2210 ppm to 1800 ppm.

SUPS MB, SUPS MD, and SUPS 3B-S are energized but disconnected from the B Battery for B Battery maintenance.

SUPS MA, SUPS MC, and SUPS 3A-S are energized and connected to the A Battery

Reactor Engineering is moving fuel within the Spent Fuel Pool

Which ONE of the following describes all of the actions required following a loss of SUPS A?

A. Stop adding PMU to the VCT. B. Stop all fuel movement in the FHB. C. Stop adding PMU to the VCT and all fuel movement in the FHB. D. No action is required since all LCOs are being met for these conditions.


Reactor Operator

Page 16 of 75


The plant is at 100% power

BATTERY CHARGER SA1 TROUBLE annunciator alarms

BOP notes that Battery A voltage is at 154 VDC

The trouble annunciator clears then re-flashes and is now locked in

RAB watch reports the charger has tripped with the HI VOLTAGE SHUTDOWN light lit

Electrical Maintenance (PME) repairs Battery Charger SA1 and the charger is returned to service

PME checks out ‘A’ Battery and reports that it meets all Category A limits Which ONE of the following Tech Spec actions is required after restoring Battery Charger SA1 to service?

A. No further action(s) is required. B. Verify battery meets Category A limits with the next 8 hours. C. Verify battery meets Category B limits within 7 days. D. Verify the battery charger will supply 132 volts at 150 amps.


Reactor Operator

Page 17 of 75


• The plant is operating at 100% power • A loss of Instrument Air has occurred • Plant Shutdown is in progress • The crew has entered OP-901-511, Instrument Air Malfunction • Instrument Air header pressure is 64 PSIG and slowly lowering

Which ONE of the following actions is required per OP-901-511?

A. Immediately trip the reactor, initiate a MSIS and perform OP-902-000, Standard Post Trip Actions.

B. Perform a rapid shutdown while attempting to restore Instrument Air Header pressure.

C. Continue plant shutdown while attempting to restore Instrument Air Header pressure.

D. Immediately trip the reactor and perform OP-902-000, Standard Post Trip Actions.


Reactor Operator

Page 18 of 75

Question 018 Following a large break LOCA, HPSI pump runout condition is prevented during the transition to Hot Leg Injection mode by __________ .

A. returning the HPSI Cold Leg Injection Flow Control valves to their SIAS positions before aligning for Hot Leg recirculation

B. closing the Orifice Bypass valves before opening the Hot Leg Injection Isolation valves

C. securing each HPSI pump before aligning it for Hot Leg Recirculation D. waiting at least 2 hours before aligning for Hot Leg Recirculation


Reactor Operator

Page 19 of 75


The Plant was operating at 100% when CEA-32 dropped into the core.

The crew has entered OP-901-102, CEA or CEDMCS Malfunction.

The crew is performing a Rapid Plant Power Reduction to comply with T.S. 3.1.3.1 action.

Which ONE of the following POWER indications should NOT be used to verify reactor power reduction?

A. Secondary Cal Power (MSBRAW) B. Turbine Power (CBTFSP) C. Delta T Power (CBDELT) D. Excore Safety Channel Powers


Reactor Operator

Page 20 of 75


• The plant is at 100% power. • Pressurizer Level controller is in AUTO. • Pressurizer Level Control select switch is in “X”. • Pressurizer Heater Low Level Cutout is selected to BOTH. • Standby Charging Pump Selector is in "AB - A". • The variable leg for RC-ILT-0110X has a leak. • No operator action is taken.

WHICH ONE of the following describes the response of the Pressurizer Level Control System?

Charging Pumps _(1)_, and Letdown flow _(2)_ . (1) (2) A. AB and A start rises B. AB and A start lowers C. AB and A get a stop signal rises D. AB and A get a stop signal lowers


Reactor Operator

Page 21 of 75


The plant is in MODE 6 with the Reactor Head removed for refueling outage.

The core offload is in progress with 52 fuel assemblies transferred to the Spent Fuel Pool storage area.

Initial Startup Count Rate Channel 1 & 2 are reading 25 cps and stable

Refueling Operator is ready to make the next grappling move

Final Startup Count Rate Channel 1 & 2 are reading 60 & 55 cps respectfully

Which ONE of the following evolutions would MOST LIKELY result in a rise in Startup Count Rate?

A. Lowering a fuel assembly into the Containment upender before transfer B. Withdrawing a fuel assembly from the core and transporting it to the upender C. Withdrawing a CEA from an assembly in the core using the CEA Mast in

Containment D. Transporting a CEA in the CEA Mast from one assembly to another in

Containment before transfer


Reactor Operator

Page 22 of 75

Question 022 The following initial conditions exist:

A Steam Generator Tube Leak is in progress

The crew has implemented OP-901-202

PSLR indicates 0.005 GPM into SG #1

PSLR indicates 0.06 GPM into SG #2

BOTH readings have been stable for over an hour

Secondary Coolant Specific Activity is 0.07 µci/gram DE I-131

Which ONE of the following conditions WILL require a Rapid Plant Power Reduction AND Shutdown to MODE 5? [Assume information update is given to the crew 35 minutes later.]

A. AE Discharge Radiation Monitor is in HIGH Alarm B. Primary to Secondary Leak is 0.070 GPM to #2 SG C. Primary to Secondary Leak is 0.085 GPM to #2 SG D. Secondary Coolant Specific Activity is 0.11 µci/gram DE I-131


Reactor Operator

Page 23 of 75


• Reactor power is at 49% and steady. • SBCS is aligned for automatic operation. • Main Feedwater Pump B startup is in progress. • Condenser vacuum begins to degrade. • Annunciator “TURBINE VACUUM LO” and “VACUUM PUMP A TRIP/TROUBLE”

are in alarm. • All available Condenser Vacuum pumps are running.

In accordance with OP-901-220, Loss of Condenser Vacuum, which ONE of the following actions should be taken by the Crew if vacuum continues to degrade? If vacuum approaches _(1)_ Hg vacuum, then trip the _(2)_ and verify _(3)_ . (1) (2) (3) A. 25” Turbine Reactor Trip B. 20” Turbine MSIVs closed C. 20” Reactor Turbine Trip D. 25” Reactor MSIVs closed


Reactor Operator

Page 24 of 75


• A discharge of Boric Acid Condensate Tank (BACT) B is in progress • The shift Chemist calls the Control Room and states that an error has been made on

the BACT ‘B’ release permit • The BM rad monitor alarm setpoint should be set at 5.5 E-3 µci/ml instead of the

current 8.5 E-3 µci/ml

Which ONE of the following procedural actions is required?

A. Continue discharge; verify initial sample results are valid and lower rad monitor alarm setpoint

B. Continue discharge while obtaining independent samples, and independently verify release rate and valve lineup

C. Secure discharge, verify discharge activity did not exceed desired setpoint, and discharge may resume after obtaining independent samples. Independently verify release rate and valve lineup.

D. Secure discharge, verify discharge activity did not exceed desired setpoint, and discharge may resume provided Rad Monitor is changed to the specified setpoint.


Reactor Operator

Page 25 of 75


The Plant in Mode 1

CROAI ‘A’ North Rad Monitor, ARM-IR-0200.1, is inoperable.

CROAI ‘B’ North Rad Monitor, ARM-IR-0200.2, failed its source check, and manual retest was unsuccessful.

Which ONE of the following actions is required within 1 hour?

A. No action is required. B. Obtain and analyze a control room ventilation grab sample every 8 hours. C. Initiate a pre-planned alternate method for monitoring the control room air intake. D. Initiate and maintain control room emergency ventilation in recirculation mode.


Reactor Operator

Page 26 of 75

Question 026 Which ONE of the following conditions will result in a Loss of Containment Integrity per Technical Specification while operating in MODE 1? A. One of two normally open redundant containment isolation valves has failed in the

CLOSE position with power removed. B. A mechanic props OPEN the Personnel Airlock outer door to perform corrective

maintenance on an inoperable inner door. C. A blank flange was installed in place of a containment isolation valve which had

failed its surveillance test. D. A manual isolation valve is CLOSED to isolate a penetration where an electrician

had disconnected the auto-close feature for a containment isolation valve.


Reactor Operator

Page 27 of 75

Question 027 During the cooldown phase of an excess steam demand accident (inside containment), the major concern is reactivity control. When the cooldown has terminated, the major concern is _______

A. pressurized thermal shock of the reactor vessel. B. inventory control of the Reactor Coolant System. C. Steam Generator tube failure after dryout on the faulted SG. D. exceeding Containment temperature and pressure limits.


Reactor Operator

Page 28 of 75

Question 028 Which ONE of the following parameters is a valid Reactor Coolant Pump (RCP) INTERLOCK that meets a required start permissive?

A. RCP Lift Oil pressure is 380 PSIG. B. Control Bleed-off pressure is 40 PSIG. C. CCW cooling water total flow is 380 GPM. D. CCW cooling water temperature is 150 ºF.


Reactor Operator

Page 29 of 75

Question 029 A plant startup following a refueling outage is in progress and the following conditions exist:

• RCS pressure is 2250 PSIA and stable • RCPs 1A, 1B, and 2A are running

Which ONE of the following temperatures (°F) is the MINIMUM allowed RCS Cold Leg temperature for this RCP pump configuration and WHY?

A. 199; Mitigate an inadvertent positive reactivity addition from colder water B. 199; Prevent excess RCP motor loading due to higher head developed by RCP 2A C. 347; Prevent excess RCP motor loading due to higher head developed by RCP 2A D. 347; Mitigate an inadvertent positive reactivity addition from colder water


Reactor Operator

Page 30 of 75

Question 030 Which ONE of the following is applied as a cover gas on the Volume Control Tank during power operations and what is the primary reason for that cover gas? A. Nitrogen; to minimize oxygen concentration in the RCS. B. Hydrogen; to minimize oxygen concentration in the RCS. C. Nitrogen; to prevent the formation of ferrous oxide corrosion layer in RCS. D. Hydrogen; to prevent the formation of ferrous oxide corrosion layer in RCS.


Reactor Operator

Page 31 of 75

Question 031 What is the power supply to SI-407 A, RC Loop 2 SDC Suction Outside Containment Isolation? A. Bus 213 A B. Bus 311 A C. Bus 314 A D. Bus 315 A


Reactor Operator

Page 32 of 75


The crew has tripped the reactor and initiated SIAS following a LOCA.

The crew is implementing OP-902-002, LOCA

Which ONE of the following combinations of pressure and flow does not meet the requirement for SIAS actuation with HPSI flow?

RCS Pressure (PSIA) SI Injection Line Flow (GPM) A. 1100 75 B. 950 115 C. 550 160 D. 150 205


Reactor Operator

Page 33 of 75


The plant is operating a 100% power

Pressurizer Safety (RC-317A) lifts and will NOT reseat

The crew initiates a manual Reactor Trip

The Quench Tank rupture disc has blown out

RCS pressure is 1000 PSIA

Containment pressure is 16.9 PSIA

Which ONE of the following temperatures (ºF) corresponds to the MAXIMUM tail pipe indication reached just prior to the rupture disc blowout?

A. 284 B. 303 C. 352 D. 400


Reactor Operator

Page 34 of 75

Question 034 The normal source of makeup to the Auxiliary Component Cooling Water Cooling Tower is the (1) and the normal source of makeup water to the Component Cooling Water Surge Tank is the (2) .

(1) (2) A. CCW Makeup Pumps Condensate Storage Tank Pumps

B. CCW Makeup Pumps Hotwell transfer Pump

C. Condensate Transfer Pump Hotwell transfer Pump

D. Condensate Transfer Pump Condensate Storage Tank Pumps


Reactor Operator

Page 35 of 75


• Plant has tripped from 100% power. • RCS pressure is 1680 PSIA and slowly lowering. • Containment pressure is 16.8 PSIA and slowly rising. • NO operator actions have been taken.

Based upon the current conditions, which ONE of the following automatic action(s) has occurred on the Component Cooling Water System?

A. CC-963A, Shutdown Heat Exchanger Outlet valve, received a FAIL OPEN signal. B. CC-620, Fuel Pool Temperature Control valve, received a FULL OPEN signal. C. CC-562, Non-Nuclear Safety Header valve, received a CLOSE signal. D. CC-200A, A Header Isolation valve, received a CLOSE signal.


Reactor Operator

Page 36 of 75

Question 036

The following plant conditions exist: • Plant is operating at 100% Power • Pressurizer Pressure Control System is aligned for normal operation

If all Pressurizer heaters fail ON (energized), which ONE of the following sequence of events (in order of actuation) will provide RCS Over-pressure protection?

A High RCS pressure Reactor Trip

Spray Valves FULL open

Pressurizer Safety Lifts

B Spray Valves FULL open

High RCS pressure Reactor Trip


C High RCS pressure Reactor Trip


Spray Valves FULL open

D Spray Valves FULL open


High RCS pressure Reactor Trip


Reactor Operator

Page 37 of 75

Question 037 While operating in MODE 1, Steam Generator 2 Pressure instrument (SG-IPT-1023A) failed LOW and these bistables were placed in BYPASS on Channel A:

LO SG-2 PRESS

HI SG-1 P

HI SG-2 P A short time later, Steam Generator 1 Narrow Range Level instrument (SG-ILT-1113C) failed LOW.

Which ONE of the following choices describes the necessary manipulations on Channel C to meet the requirement in Tech Specs within ONE HOUR?

1 2 3 A. Bypass LO SG-1 LVL Bypass HI SG-1 LVL Trip HI SG-1 P B. Trip LO SG-1 LVL Trip HI SG-1 LVL Bypass HI SG-1 P C. Bypass HI SG-1 LVL Trip HI SG-2 P Bypass HI SG-1 P D. Bypass LO SG-1 LVL Trip HI SG-2 P Trip HI SG-1 P


Reactor Operator

Page 38 of 75

Question 038 Which ONE of the following is the normal power supply to Core Protection Calculator Channel B on CP-7? A. 125 VDC Bus A-DC B. 125 VDC Bus B-DC C. SUPS MA D. SUPS MB


Reactor Operator

Page 39 of 75

Question 039 Which ONE of the following Engineered Safety Features Actuation Signals (ESFAS) will reset AUTOMATICALLY when the condition clears? A. CIAS to FP-601A, Containment Isolation Fire Water A B. EFAS to EFW-228A, Emergency Feedwater Isolation SG 1 Primary C. SIAS to EFW-223A, Emergency Feedwater Flow SG 1 Backup D. SIAS to SI-139A, LPSI Flow Control Cold Leg 2A


Reactor Operator

Page 40 of 75


The plant has experienced a Loss of Coolant Accident inside containment

The crew has entered OP-902-000 and is performing Standard Post Trip Actions

Containment Pressure is 16.9 PSIA and slowly rising

Containment Temperature is 205°F and slowly rising

Which ONE of the following actions is required based upon this information?

A. Manually initiate Containment Spray. B. Manually initiate Main Steam Isolation. C. Initiate use of Harsh Environment values. D. Verify all Containment Fan Coolers are running in FAST speed.


Reactor Operator

Page 41 of 75


• A Loss of Offsite Power has occurred • EDG B started, then tripped on Generator Differential • A fault on the 3A Bus has prevented loading on the bus • Offsite power has been restored and the 2B Bus is energized • The crew is attempting to restore power to a safety bus

Which ONE of the following actions will be required to restore power to Containment Spray Pump B in accordance with OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery?

A. Close 3B-S To 2B Tie, then Close 2B To 3B-S Tie. B. Close 2B To 3B-S Tie, then Close 3B-S To 2B Tie. C. Reset Generator Differential trip and allow EDG B to start. D. Close 2B To 3B-S Tie, then take EDG B key-switch to Bus Tie.


Reactor Operator

Page 42 of 75

Question 042 Plant conditions are as follows:

A LOCA has occurred in Containment.

NO ESFAS actuations have been reset.

Which ONE of the following conditions satisfies a Containment Spray Termination criterion?

A. RAS has actuated and Containment temperature has dropped to 120 °F B. Containment Spray is required for continued Iodine removal. C. Containment PIG radiation monitor readings are NOT in alarm D. Containment pressure has been reduced to 16.2 PSIA and dropping.


Reactor Operator

Page 43 of 75


Plant is in MODE 3

FWCS is in manual with the Auxiliary Feedwater Pump in manual

A Steam Line break occurs

SG 1 pressure is 650 PSIA and lowering

SG 2 pressure is 700 PSIA and rising

Containment pressure is 15.1 PSIA and stable

Which ONE of the following conditions describes the availability of Main Feedwater to the Steam Generators?

A. MFW is NOT available to either SG. B. MFW is available to SG 1 using the Auxiliary Feedwater pump C. MFW is available to SG 2 using the Auxiliary Feedwater pump D. MFW is available to SG 1 and SG 2 using the Auxiliary Feedwater pump


Reactor Operator

Page 44 of 75


• A plant power reduction is in progress • Reactor power is 58% and slowly lowering • Main Feedwater pumps A & B are providing Feedwater in AUTO mode • The BOP reports Feedwater Master Controller #1 has failed LOW. • The BOP reports NO response while attempting to operate the Master Controller #1

in MANUAL.

Which ONE of the following valves should be operated in MANUAL mode to restore and maintain Steam Generator level within band? (Consider each response independently)

A. Main Feedwater Regulating valve #1 M/A station B. Startup Feedwater Regulating valve #1 M/A station C. Main Feedwater Pump Speed #1 M/A station D. Both the SUFRV #1 M/A station and Main Feedwater Pump Speed #1 M/A station


Reactor Operator

Page 45 of 75


The plant is operating at 100%

Steam Generator 2 Steam Flow transmitter to Feedwater Control failed LOW.

The BOP operator took manual control of FWCS Master Controller #2, but the reactor tripped on Low Steam Generator Level.

All other Feedwater Controllers are in AUTOMATIC.

As a result of the BOP’s action, Reactor Trip Override will….

A. function as designed on SG #2; no contingency actions are required. B. not function on SG #2; the BOP must manually set FWCS Master Controller #2 to

5%. C. not function on SG #2; the BOP must manually close MFRV #2 and position

SUFRV #2 to 13 – 21% open. D. not function on SG #2; the BOP must manually close MFRV #2, position SUFRV

#2 to 13 – 21% open and set MFP B speed to minimum.


Reactor Operator

Page 46 of 75

Question 046 Which ONE of the following conditions would meet initiation criteria for Diverse Emergency Feedwater Actuation (DEFAS) logic? A. DRTS has NOT actuated. B. EFAS-1 has NOT actuated. C. Both SG pressures are 675 PSIA on 2 of 2 Pressure Transmitters D. Both SG wide range (WR) levels are 54% (SG1) and 53% (SG2) respectively on 2 of

2 Level Transmitters


Reactor Operator

Page 47 of 75


The reactor has tripped Pressurizer Pressure is 1750 PSIA and lowering SG #1 Level is 40% WR and lowering SG #2 Level is 51% WR and stable SG #1 Pressure is 600 PSIA SG #2 Pressure is 750 PSIA Containment Pressure is 15.2 PSIA and stable ALL safety systems have responded as designed

Which ONE of the following conditions describes the initial response of Emergency Feedwater to this event and the procedural requirement to meet safety function for RCS heat removal?

EFW Flow (GPM) SG Level A. SG #1 = 400; SG #2 = 200 50% to 70% NR B. SG #1 = 0; SG #2 = 200 50% to 70% NR C. SG #1 = 0; SG #2 = 200 60% to 80% WR D. SG #1 = 400; SG #2 = 400 60% to 80% WR


Reactor Operator

Page 48 of 75


A loss of Off-Site power has occurred. The crew has entered OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery.

All indications for this condition are normal with the following exceptions:

Auxiliary Cooling Water Pump B tripped at the 17 second load block

All EDG B Sequencer load block lights have extinguished

EDG B Sequencer LOCKOUT light is LIT For the above indications, the (1) deenergized and necessary actions to restore power to all Train B safety components requires racking-down the ACCW Pump B breaker, then placing the Sequencer control switch on CP-1 to (2)

(1) (2) A. entire 3B safety Bus is RESET.

B. entire 3B safety Bus is TEST.

C. Train B load blocks after block 17 are RESET.

D. Train B load blocks after block 17 are TEST.


Reactor Operator

Page 49 of 75

Question 049 Which ONE of the following conditions describes the capability of breaker operation following a loss of DC control power to 4160 V and 480 V switchgears?

AUTO REMOTE MANUAL LOCAL MANUAL A. DISABLED DISABLED WORKS B. DISABLED DISABLED DISABLED C. DISABLED WORKS WORKS D. WORKS DISABLED DISABLED


Reactor Operator

Page 50 of 75

Question 050 Emergency Diesel Generator A was run in the test mode for surveillance testing. After the test was complete, Fuel Oil Storage Tank A level is 38,250 gallons. The 7 day minimum limit is 40,033 gallons and the 5 day minimum limit is 37,696 gallons. It is acceptable to remain in this condition provided (1) within (2) .

(1) (2)

A. Fuel Oil Storage Tank A level is restored above 40,033 gals

24 hours

B. Fuel Oil Storage Tank A level is restored above 40,033 gals

48 hours

C. replacement Fuel on site 24 hours

D. replacement Fuel on site 48 hours


Reactor Operator

Page 51 of 75

Question 051 Annunciator EDG A UNAVAILABLE has come in at CP-1. This alarm is in because ___ A. EDG A failed to trip on generator over current during a LOCA. B. EDG A tripped on generator differential during a loss of off site power. C. the SERVICE WATER FLOW LOW annunciator came in locally during EDG cooldown. D. the STARTING AIR SYSTEM LOW PRESS annunciator came in locally during EDG

start.


Reactor Operator

Page 52 of 75

Question 052 The crew has entered OP-901-202, Steam Generator Tube Leakage or High Activity, due to rising activity in the secondary. Which ONE of the following radiation monitors (1) is specified as the primary monitor with the designed sensitivity to measure small Primary to Secondary leakage AND which radiation monitor (2) is specified as qualified for use if the primary monitor fails?

(1) (2)

A. MS Line N-16 Monitor PRM-RE5501-1 (2)

Condenser Vacuum Pump Monitor

PRM-IRE-0002 B. MS Line N-16 Monitor

PRM-RE5501-1 (2) AE Discharge Monitor

PRM-IRE-0004 C. AE Discharge Monitor

PRM-IRE-0004 Condenser Vacuum Pump

Monitor PRM-IRE-0002

D. AE Discharge Monitor PRM-IRE-0004

MS Line N-16 Monitor PRM-RE5501-1 (2)


Reactor Operator

Page 53 of 75

Question 053 The following conditions exist:

ACC Pump A is OFF with the control switch in AUTO

While in this alignment, ACC Jockey Pump A trips and cannot be started

Which ONE of the following describes the automatic response of the ACC/CCW system?

A. Low Header Pressure would start the ACC Pump ‘A’. B. Rising CCW Header A temperature would split the A & B CCW trains. C. Low Header Pressure would cycle ON the required Dry Cooling Tower ‘A’ Fans. D. Rising CCW Header A temperature would open CCW A Dry Cooling Tower

bypass.


Reactor Operator

Page 54 of 75

Question 054 The following plant conditions exit:

• Instrument Air Compressor ‘A’ is in AUTO and running unloaded. • Instrument Air Pressure Header pressure is currently 110 PSIG and lowering.

If Instrument Air pressure were to drop to 94 PSIG, what would be the status of the Instrument Air system lineup with NO operator action? IA Dryer Bypass SA Backup Supply IA-123 SA-125

A. CLOSED CLOSED B. OPEN CLOSED C. CLOSED OPEN D. OPEN OPEN


Reactor Operator

Page 55 of 75

Question 055 A plant trip and SIAS have occurred due to low Pressurizer pressure. What is the expected range of Containment Annulus to ambient differential pressure in inches of water?

A. -3.0 to -8.0 B. +2.0 to -8.0 C. -3.0 to -10.0 D. +2.0 to -10.0


Reactor Operator

Page 56 of 75

Question 056 Which ONE of the following alarms would be the FIRST indication of a leaking Pressurizer Safety Valve?

A. Pressurizer Level High/Low B. Containment Water Leakage High C. Quench Tank Temperature High D. Reactor Drain Tank Level High/Low


Reactor Operator

Page 57 of 75


The reactor is operating at 95% power and stable

Pressurizer Level is 53%

Charging Pump ‘B’ is running with ‘A’ & ‘AB’ in STANDBY

Letdown flow is 40 GPM with the NORMAL Letdown Flow Control (FCV) valve and Backpresure Regulating (BPRV) valve in service

The “Letdown Low Flow “alarm was just received. Letdown flow indicates ZERO (0).

Letdown FCV controller output is at 100%.

NORMAL Letdown Flow Control (FCV) valve indicates closed

Backpresure Regulating (BPRV) valve controller output is at 0%.

NORMAL Backpresure Regulating (BPRV) valve indicates closed.

Crew has entered OP-901-112, Charging or Letdown Malfunction procedure. Which ONE of the following actions will be required for these conditions?

A. Place FCV M/A to MANUAL and raise the flow. B. Place ALTERNATE Letdown BPRV in service. C. Place ALTERNATE Letdown FCV in service. D. Secure both Charging and Letdown.


Reactor Operator

Page 58 of 75


A Loss of Offsite Power has occurred

Emergency Feedwater is providing flow to both Steam Generators

SG #1 pressure is 690 PSIA

SG #2 pressure is 705 PSIA

Pressurizer pressure is 1700 PSIA

Which ONE of the following temperatures (ºF) represents the MINIMUM subcooling margin required by procedure?

A. Loop 1 Hot Leg Temperature is 520 B. Loop 2 Hot Leg Temperature is 532 C. Representative Core Exit Temperature is 554 D. Representative Core Exit Temperature is 585


Reactor Operator

Page 59 of 75

Question 059 The plant conditions are as follows:

Pressurizer pressure is 1550 PSIA and lowering

S/G #1 Narrow Range level is 15% and lowering

S/G #2 Narrow Range level is 18% and lowering

S/G #1 Wide Range level is 68% and lowering

S/G #2 Wide Range level is 69% and lowering

Both S/G pressure are 695 PSIA and lowering

Containment pressure is 15.1 PSIA and steady

An EFAS signal will be generated by __(1)__ and the low Pressurizer Pressure will generate a __(2)__.

(1) (2) A. S/G #1 Narrow Range Level SIAS actuation

B. S/G #2 Narrow Range Level MSIS actuation

C. S/G #1 Wide Range Level SIAS actuation

D. S/G #2 Wide Range Level MSIS actuation


Reactor Operator

Page 60 of 75

Question 060 Which ONE of the following design features will prevent or mitigate an inadvertent draining of the Spent Fuel Pool?

A. Fuel Pool CMU makeup valve automatically opens on a LOW level alarm. B. Fuel Pool Purification pump suction line piping has drilled holes that act as an anti-

siphon device. C. Fuel Pool Cooling pump suction line piping has drilled holes that act as an anti-

siphon device. D. Fuel Pool piping system, including pumps and valves, are located at or above the

normal operating water level.


Reactor Operator

Page 61 of 75


The plant is at 75% power

A loss of Computer SUPS caused a spurious operation of the SBCS which resulted in MS-319A and MS-320A opening and remaining OPEN.

Disregarding the effects of Moderator Temperature and Doppler coefficients, which ONE of the following reactor power levels will be the approximate resulting plant output?

A. 55% B. 65% C. 85% D. 95%


Reactor Operator

Page 62 of 75


The plant is operating at 85% power.

The crew is preparing to remove the A2 waterbox from service.

The CRS directs the ATC to remove Cutback from service and place Reactor trip on Turbine trip in service.

After Cutback was removed from service, but prior to Reactor Trip on Turbine Trip being enabled, the Main Generator tripped.

Prior to any automatic trip, RCS temperature and pressure would __(1)__. The automatic trip signal that would actuate FIRST to cause a reactor trip would be __(2)__.

(1) (2)

A. Lower Low DNBR

B. Rise High Linear Power

C. Lower Low RCS Pressure

D. Rise High Pressurize Pressure


Reactor Operator

Page 63 of 75


Power Ascension is in progress

CEA Channel Deviation alarm just occurred, followed by a CEA Group Major Deviation alarm.

Group ‘P’ rod withdrawal was in progress, but is now stopped. Power is currently 85%. Group ‘P’ rods are reading: o CEA 24 at 144.5” o CEA 25 at 138” o CEA 26 at 139.5” o CEA 27 at 146”

Group P CEAs are trippable, but cannot be inserted or withdrawn. Given these conditions, a power reduction to (1) power is required. Once the power reduction and repairs are complete, the crew will (2)

(1) (2)

A. 60 % borate as necessary to restore rod configuration.

B. 60 % reset ACTM cards for CEA 25 & 26.

C. 55 % borate as necessary to restore rod configuration.

D. 55 % reset ACTM cards for CEA 25 & 26.


Reactor Operator

Page 64 of 75

Question 064 Which ONE of the following radiation monitors will cause an AUTO closure of Waste Gas Discharge FCV (GWM-309) valve during a Gaseous Waste Discharge evolution?

A. Waste Gas Discharge Rad Monitor B. Plant Stack PIG Monitor A or B C. Plant Stack WRGM Monitor D. RAB HVAC PIG Monitor B


Reactor Operator

Page 65 of 75

Question 065 The power supply for ARM-IRE-200.1, Control Room Outside Air Intake (CROAI) A North Radiation Monitor, has failed.

As a result, __(1)__ and the operator__(2)__.

___(1)___ ___(2)___ A. CR Emergency Filtration Unit A

started and CR Toilet Exhaust Fan B stopped

should manually start the CR Toilet Exhaust Fan B

B. CR Emergency Filtration Unit A started and CR Toilet Exhaust Fan B stopped

cannot restore either component until the rad monitor is repaired

C. both CR Emergency Filtration Units A & B started

should manually secure CR Emergency Filtration Unit B

D. both CR Emergency Filtration Units A & B started

cannot restore either component until the rad monitor is repaired


Reactor Operator

Page 66 of 75

Question 066 With the plant in Mode 4, shift staffing requirements require (1) and either the (2) with a valid SRO license, can hold the Control Room Command function.

(1) (2)

A. 1 reactor operator SM or STA,

B. 1 reactor operator SM or CRS,

C. 2 reactor operators SM or STA,

D. 2 reactor operators SM or CRS,


Reactor Operator

Page 67 of 75

Question 067 In accordance with OP-010-004, Power Operations, which ONE of the following general precautions, limitations, and notes is valid for proper ASI control? A. Control ASI at ± 0.005 of ESI during steady-state operations. B. When Equilibrium Shape Index (ESI) is not known, then maintain ASI as close to 0.0

as possible until ESI can be determined. C. CEDMCS will be operated in Manual Sequential mode for ASI control. D. Do not insert Group 5, 6 or P CEAs below 105 inches withdrawn


Reactor Operator

Page 68 of 75


Component Cooling Water Pump AB has been aligned to replace CCW Pump A

Local and remote breaker indicating lights are OFF

Which ONE of the following conditions describes the reason for NO indicating lights? [Reference CWDs provided.]

A. Aux Panel Transfer Switch aligned to Control Room B. Breaker fully racked up C. Closing Fuses Blown D. Tripping Fuses Blown


Reactor Operator

Page 69 of 75

Question 069 Which ONE of the following statements would meet the criteria for a LOCKED component in accordance with OP-100-009, Control of Valves and Breakers? A. A normally closed and capped vent or drain valve B. A remotely operated isolation valve which receives an ESF signal C. A manual isolation valve in the suction flow path for a non-safety related pump D. A remote manual isolation valve which does not receive an ESF actuation signal, but

is required to be secured in the closed position for Containment isolation


Reactor Operator

Page 70 of 75

Question 070 Which ONE of the following documents contains the NRC authorization for Waterford 3 to operate at a MAXIMUM reactor core power level of 3716 MWth?

A. Tech Spec Section 6.0, Administrative Controls

B. Tech Spec Section 5.0, Design Features

C. Waterford 3 Facility Operating License

D. Final Safety Analysis Report


Reactor Operator

Page 71 of 75

Question 071 As an Emergency Team member following a LOCA in Containment event, you will enter the Containment in order to isolate the leak.

Which ONE of the following exposures will meet the maximum limit allowed for these conditions?

TEDE REM

Lens of the Eye REM

A. 10 75

B. 10 30

C. 25 75

D. 25 30


Reactor Operator

Page 72 of 75

Question 072 With the plant in Mode 1, which ONE of the following entry areas can you access with a General Radiation Work Permit vice requiring a Specific Radiation Work Permit?

A. Purification Ion Exchanger ‘A’ Room

B. Spent Resin Tank Room

C. -35 Wing Area

D. VCT Room


Reactor Operator

Page 73 of 75

Question 073 Which ONE of the following statements describes a general expectation for EOP usage in accordance with OI-038-00, Emergency Operating Procedures – Operations Expectations / Guidance or OP-100-017, Emergency Operating Procedure Implementation Guide?

A. Steps in the EOPs are expected to be performed in the correct sequence, except for continuously applicable steps marked with asterisks.

B. Verification of an RCS temperature response to a plant change during natural circulation cannot be accomplished until approximately 20 to 25 minutes following the action.

C. Where multiple indications for one parameter exist, use PMC indication before control panel indication.

D. The operating crew should monitor the Safety Function Status Checklist every 30 minutes.


Reactor Operator

Page 74 of 75


Main Feedwater Regulating Valve #1 failed closed.

The plant tripped from 100% power on low Steam Generator level. Based on the guidance in OI-038-000, Emergency Operating Procedure Operations Expectation/Guidance, on information reporting during EOP usage, which ONE of the following conditions should the BOP/ATC operators report to the Control Room Supervisor during their performance of Standard Post Trip Actions?

A. All 3 Charging Pumps are running. B. MS-401A, EFW Pump AB Supply 1, is closed. C. All 3 Emergency Feedwater Pumps are running. D. Startup Feedwater Regulating Valve #1 is 18% open.


Reactor Operator

Page 75 of 75

Question 075 The minimum Emergency Plan Classification for activating the Emergency Response Data System (ERDS) is __(1)__ and the required maximum time to activate ERDS is __(2)__ minutes from the time of classification.

(1) (2)

A. Unusual Event 30

B. Unusual Event 60

C. Alert 30

D. Alert 60

U.S.N.R.C. Site-Specific Written Examination Waterford 3

Senior Reactor Operator

Page 1 of 25

Question S01 The following plant conditions exist: • The plant is at 15% power • The crew is making preparations to synch the Main Generator to the grid • Main Feedwater Pump ‘B’ is operating in manual control • Startup Transformer ‘A’ trips on the Sudden Pressure Relay causing a reactor trip on

loss of RCP 1A and 2A • SG#1 level is 30% NR and rising • SG#2 level is 25% NR and rising • SG#1 pressure is 900 PSIA and rising • SG#2 pressure is 880 PSIA and rising • Pressurizer pressure is 2000 PSIA and rising • Pressurizer level is 15% and rising with 3 Charging Pumps running • RCS Temperature is 540 F and rising • EDG ‘A’ is running loaded Which of the following procedures would the CRS diagnose for entry? (Assume all components not discussed functioned as required.) A. OP-902-001, Reactor Trip Recovery with OP-901-310, Loss of Train A Safety Bus B. OP-902-001, Reactor Trip Recovery with OP-901-112, Charging or Letdown

Malfunction C. OP-902-006, Loss of Main Feedwater Recovery with OP-901-310, Loss of Train A

Safety Bus D. OP-902-006, Loss of Main Feedwater Recovery with OP-901-112, Charging or

Letdown Malfunction



Page 2 of 25

Question S02 The following plant conditions exist:

The plant tripped from 100% The plant has experienced a LOCA event RCS pressure is 540 PSIA and dropping Containment pressure is 26.2 PSIA and steady Representative CET temperatures are 470 º F and steady RVLMS levels 1-4 indicate not covered RVLMS levels 5-8 indicate covered All systems have responded per design

These conditions describe the characteristics of a (1) and core cooling (2)

(1) (2)

A. Large Break LOCA is satisfied through break flow and core boil off, and maintained by Long Term Cooling

B. Large Break LOCA requires the use of Steam Generators, with a cooldown to Shutdown Cooling entry condition.

C. Small Break LOCA is satisfied through break flow and core boil off, and maintained by Long Term Cooling

D. Small Break LOCA requires the use of Steam Generators, with a cooldown to Shutdown Cooling entry condition.



Page 3 of 25


RCS temperature is 185 °F and rising slowly

RCS level is 14 feet and steady

Shutdown Cooling Train ‘A’ is in service with flow 600 to 1000 GPM and oscillating

LPSI Pump ‘A’ amps indicate 10 to15 amps and oscillating

The RCA watch reports that LPSI Pump A is running with a rattling sound

The crew has entered OP-901-131, Shutdown Cooling Malfunction. Which ONE of the following procedural sub-sections is appropriate based on these indications?

A. E1. System Leakage

B. E2. Loss of Shutdown Cooling Flow

C. E3. Loss of Shutdown Cooling Heat Removal Capability

D. E4. System Malfunction in Mode 4



Page 4 of 25


The plant was operating at 100% power with EDG A danger tagged An Excess Steam Demand occurred SIAS, CIAS, and MSIS have been initiated The Pressurizer level is 0% After entering OP-902-004, Excess Steam Demand Recovery, the

following conditions change: Representative CET temperature and RCS pressure start to rise. A Loss of Off Site Power occurs

All components respond as designed to the event. Based on these conditions, the CRS will (1) and (2)

(1) (2)

A. Remain in OP-902-004 Direct the ATC to stabilize RCS pressure above HPSI Pump shutoff head.

B. Remain in OP-902-004 Direct the ATC to stabilize RCS pressure below HPSI Pump shutoff head.

C. Exit OP-902-004 and enter OP-902-008, Functional Recovery

Direct the ATC to stabilize RCS pressure above HPSI Pump shutoff head.

D. Exit OP-902-004 and enter OP-902-008, Functional Recovery

Direct the ATC to stabilize RCS pressure below HPSI Pump shutoff head.



Page 5 of 25


The plant is in Mode 1 when annunciator SUPS MC TROUBLE alarms on CP-1 The RAB watch is sent to SUPS MC and reports alarm LOW DC VOLTAGE

FROM BATTERY is locked in. Additionally, breaker ID-EBRK-1A-38, SUPS MC Emergency Supply, is tripped

open SUPS MC voltage output is 122 VAC and steady All other SUPS parameters are normal The CRS refers to off normal procedure OP-901-312, Loss of Vital Instrument

Bus, which directs him to Tech Spec 3.8.3.1. Based on these indications, the CRS will

A. NOT enter Tech Spec 3.8.3.1, but must restore the SUPS MC alignment within 24 hours.

B. Enter Tech Spec 3.8.3.1 action b and be required to restore the SUPS MC alignment within 2 hours.

C. Enter Tech Spec 3.8.3.1 action b and be required to restore the SUPS MC alignment within 24 hours.

D. Enter Tech Spec 3.8.3.1 action c and be required to restore the SUPS MC alignment within 2 hours.



Page 6 of 25


The plant is in Mode 1 The shift manager receives a call from the grid operator informing him that

Waterford’s post-trip grid voltage would be 222 kV, which is below the required value of TRM 3.8.1.1 for post-trip emergency loads

Current grid voltages meet the requirements of OP-903-066, Electrical Breaker Alignment Check.

Based on this information, the crew should (1) because (2)

(1) (2)

A. declare both AC off-site circuits inoperable and enter both Tech Spec 3.8.1.1 and TRM 3.8.1.1

sufficient margin does not exist to ensure offsite power would remain available for either safe shutdown of the facility or for the mitigation of any accidents.

B. declare both AC off-site circuits inoperable and enter both Tech Spec 3.8.1.1 and TRM 3.8.1.1

sufficient margin exists to ensure offsite power would remain available for safe shutdown of the facility, but not for the mitigation of any accidents.

C. enter only TRM 3.8.1.1 Sufficient margin exists to ensure offsite power would remain available for safe shutdown of the facility, but not for the mitigation of any accidents.

D. enter only TRM 3.8.1.1 Sufficient margin exists to ensure offsite power would remain available for operation of the emergency loads following a design basis accident.



Page 7 of 25


A power reduction is in progress to repair Main Feedwater Pump A. Power is 80% Group P CEAs are at 110 inches for ASI control Group P CEAs went below 120 inches 1 hour ago

On the next CEA insertion, Group P CEAs continued to insert after the ATC released the shim switch.

The CEDMCS Mode Select switch was taken to OFF. All Group P CEAs stopped at 105 inches. I&C technicians have determined the fault to be in a common relay for Group P Group P remains trippable. Further Group P movement will not be possible until the relay is replaced.

Based on this failure, the CRS declares the CEAs in Group P inoperable and enters…

A. Only Tech Spec 3.1.3.1 and must restore operability within 72 hours. B. Only Tech Spec 3.1.3.6 and must restore Group P insertion limits within 2 hours. C. Only Tech Spec 3.1.3.6 and must limit any subsequent power increase to < 5%

per hour. D. Both Tech Specs 3.1.3.1 and 3.1.3.6, and must restore Group P insertion limits

within 2 hours.



Page 8 of 25


The plant was operating at 100%

S/G #1 primary to secondary leakage is 80 GPD and rising

Charging Pump ‘A’ is tagged out for seal replacement

The leak degrades and Letdown flow goes to minimum If the rate of change in primary to secondary leakage rises to (1) GPD/HR,

then the CRS should implement OP-901-212, Rapid Plant Power Reduction. If the rate of primary to secondary leakage rises to (2) GPM, the

CRS should direct a Reactor trip with SIAS and CIAS.

(1) (2) A. 15 44

B. 15 88 C. 30 44 D. 30 88



Page 9 of 25

Question S09 During a refueling outage with fuel movement in progress, which ONE of the following would be considered a loss of Containment Closure? A. Equipment hatch is closed and secured by four symmetrically spaced bolts. B. Both Containment Personnel Airlock doors simultaneously open with one being

capable of being closed. C. Containment Purge valves are open with a Purge in progress and one Containment

Purge Radiation Monitor inoperable. D. SG Secondary side manways are off and a Main Steam Safety Valve is removed,

with the capability of being isolated within 1 hour.



Page 10 of 25

Question S10 The following plant conditions exist: • A Main Steam Line Break has occurred on SG #2 • The reactor tripped on Low Steam Generator Pressure • SG #2 has just blown dry and the CRS has ordered performance of the necessary

steps of OP-902-004 to stabilize RCS temperature and pressure Which ONE of the following states the reason for feeding the LEAST affected SG with EFW manually? A. To restore subcooled margin to with the P-T Curve limits B. To reduce the positive reactive addition from the rapid cooldown C. To provide additional cooling since the ADV alone will not provide sufficient cooling D. To override the Main Steam Isolation Signal that blocks the automatic Emergency

Feedwater signal.



Page 11 of 25


The plant at 100% power

Annunciator VCT LEVEL LO-LO is received

The ATC operator reports VCT level indicates 45% and steady on CP-4

The ATC also reports the annunciator response procedure lists CVC-ILT-0227 as the source instrument for the locked in alarm.

Based on this report the CRS enters (1) because (2)

(1) (2)

A. OP-901-113, Volume Control Tank Makeup Control Malfunction,

Because the VCT discharge valve has closed and the RWSP to Charging Pump valve has opened to add borated water to the RCS.

B. OP-901-113, Volume Control Tank Makeup Control Malfunction,

Because VCT automatic makeup capability has been lost.

C. OP-901-112, Charging Letdown Malfunction,

Because a VCT level instrument failure caused the Charging Pumps to loose suction.

D. OP-901-112, Charging Letdown Malfunction,

Because Letdown flow to the VCT has been secured and Pressurizer level will begin rising.



Page 12 of 25


A SGTR event is in progress with S/G #2 faulted The crew has completed the rapid cooldown of the RCS RCS THOT is 513 °F RCS TCOLD is 504 °F RCS pressure is 1450 PSIA S/G #2 pressure is 650 PSIA Reactor Coolant Pumps 1B and 2B are operating OP-902-007, Steam Generator Tube Rupture Recovery directs the reduction of

RCS pressure. Based on plant conditions, the CRS should direct the ATC to reduce RCS pressure, with a MINIMUM pressure of A. 700 PSIA B. 940 PSIA C. 1000 PSIA D. 1100 PSIA



Page 13 of 25


The plant is in Mode 1 Channel ‘B’ Wide Range Pressurizer Pressure transmitter has failed LOW Appropriate bistables have been bypassed on Channel ‘B’ Subsequently, Channel ‘C’ LOW Pressurizer Pressure bistable has failed in the

actuated state. If the CRS directs bypassing the Channel ‘C’ Low Pressurizer Pressure bistable, then A. Channel ‘B’ HIGH Pressurizer pressure remains bypassed and Channel ‘C’ LOW

Pressurizer pressure remains bypassed. No additional actions are required. B. Channel ‘B’ LOW Pressurizer pressure remains bypassed, Channel ‘C’ does not

bypass. Channel ‘C’ must be placed in trip to comply with Tech Specs. C. A Reactor trip and SIAS occur. 32A and 32B feeder breakers must be closed to

regain Pressurizer Heaters. D. A SIAS occurs. HPSI pumps must be secured to stop the Pressurizer level rise.



Page 14 of 25


The plant is operating at 100% power Emergency Feedwater Pump A is danger tagged out CRS directed a reactor trip due to a loss of both Main Feedwater Pumps The crew has entered OP-902-006, Loss of Main Feedwater Recovery EFW Pump AB tripped following announcement of entry into OP-902-006

If the current plant conditions existed for 30 minutes, then the appropriate guidance in OP-902-006 for these conditions would be to (1) because (2)

(1) (2)

A. trip 2 Reactor Coolant Pumps

securing all RCPs is only required for a loss of all Feedwater.

B. trip 2 Reactor Coolant Pumps

securing 2 RCPs will lower heat input to the RCS to be within the capacity of the EFW system.

C. trip 4 Reactor Coolant Pumps

securing all RCPs is required whenever EFW Pump AB is not available in OP-902-006.

D. trip 4 Reactor Coolant Pumps

the capacity of a single motor driven EFW pump capacity is not adequate for this point in the event.



Page 15 of 25


A Loss of Off-Site Power (LOOP) event occurred The crew entered OP-902-003, Loss of Offsite Power/Loss of Forced Circulation

Recovery procedure The BOP verified ALL loads had sequenced onto the Safety Buses.

The following alarms are received a short time later: EDG B TROUBLE annunciator is in alarm on CP-1

LOCAL alarms for EDG B: o STBY Fuel Oil Booster Pump Running/Trouble o Lube Oil Filter High Differential Press

EDG A UNAVAILABLE annunciator is in alarm on CP-1 LOCAL alarms for EDG A:

o Day Tank Level Low o Starting Air System Low Pressure

Which ONE of the following EDG conditions must be addressed FIRST by the CRS and WHY?

A. EDG A Day Tank Level; A loss of fuel oil supply capability will result in EDG trip. B. EDG B Fuel Oil Booster Pump; A loss of fuel oil pumping capability will result in

EDG trip. C. EDG A Starting Air Pressure; A loss of air pressure will prevent restart of the EDG

upon a trip or other malfunction. D. EDG B Lube Oil Filter High Differential Press; flow will bypass filter, eliminating

filtering action.



Page 16 of 25

Question S16 Given the following:

You are reviewing a work order that requires removing QSPDS 1 from service as the Work Management Center SRO.

After obtaining a copy of OP-903-013, Monthly Channel Checks, and the current EOS log, you note the following core exit thermocouples are listed as INOPERABLE:

A-14 C-6 E-2 G-4 G-2 G-9 L-2 L-13 T-20

Which ONE of the following T.S. 3.3.3.6 LCO conditions would apply for the planned work and WHY?

A. LCO is met; adequate number of CETs per quadrant exist. B. LCO is NOT met: Quadrant 1 operable CETs are less than required

number. C. LCO is NOT met: Quadrant 2 operable CETs are less than required

number. D. LCO is NOT met: Quadrant 1 & 2 operable CETs are less than required

number.



Page 17 of 25


The plant is MODE 6 and core reload is in progress

Fuel Handling Building Normal Ventilation Train A is in service.

Two minutes ago the crew received a report of a dropped fuel assembly in the Fuel Handling Building

A Fuel Handling Accident (FHA) Signal has not yet been generated

Crew has implemented OP-901-405, Fuel Handling Incident. Based on these conditions, the crew should expect the (1) to detect any initial airborne activity rise and should start the (2) following the FHA signal.

(1) (2)

A. Fuel Handling Building PIG A Radiation Monitor

Fuel Handling Building HV Room Exhaust Fan A

B. Fuel Handling Building PIG A Radiation Monitor

FHB WRGM sample pump

C. Fuel Handling Building WRGM

Fuel Handling Building HV Room Exhaust Fan A

D. Fuel Handling Building WRGM

FHB WRGM sample pump



Page 18 of 25


Waste Condensate Tank (WCT) ‘B’ is being discharged to the Circ Water system EFFLUENT RAD MONT SYS ACT HI-HI annunciator is in alarm on CP-36 WASTE LIQUID RAD MONITOR TROUBLE annunciator is in alarm on CP-4 PRM-IRE-0647, Liquid Waste Radiation monitor, indicates rising activity level The ATC operator reports that both LWM-441 and LWM-442 indicate OPEN.

In accordance with OP-901-412, Liquid Waste Discharge High Radiation, the CRS should direct the operator (in order of significance) to (1) then (2) (1) (2) A. Stop the WCT ‘B’ pump and

close WCT discharge valve call Chemistry to evaluate release

relative to dose limits in Offsite Dose Manual

B. place CS for LWM-441 and LWM-442 in the CLOSED position and verify closed

verify the Rad alarm is valid by checking Liquid Waste Discharge

Recorder

C. verify LWM discharge flow is less than the flow rate specified

in the release permit

stop the WCT ‘B’ pump and close WCT discharge valve

D. call Chemistry to direct a sample for isotopic analysis of

tank discharge

place CS for LWM-441 and LWM-442 in the CLOSED position and

verify closed



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Question S19 The plant has commenced the transition from Mode 6 to perform a Reactor Startup following a refuel outage. Which ONE of the following activities could cause a positive reactivity excursion requiring implementation of OP-901-104, Inadvertent Positive Reactivity Addition?

A. Starting the first RCP with a diluted pocket of RCS water in that loop. B. Starting the third RCP with Shutdown Cooling at maximum cooling capacity C. Placing Pressurizer Level Controller in AUTO with a large positive deviation signal

input. D. Raising Steam Generator level from 50% to 60% NR with AFW flow.



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Question S20 The SRO on shift that holds Control Room Command and Control is responsible for all of the following EXCEPT: A. Ensuring immediate actions are initiated under transient or accident conditions. B. Authorizing deviation from license conditions as allowed by 10 CFR 50.54(x). C. Act as the Emergency Coordinator when the emergency plan is implemented. D. Operating the plant safely and within the limitations of administrative and regulatory

requirements.



Page 21 of 25

Question S21

The Shift Manager has directed you to prepare for emergent work on a safety related piece of equipment.

A full EOS Checklist will be required to be filled out unless the (1) and there are no (2)

(1) (2)

A. work will be completed during the same shift it was removed

Fire Impairments required.

B. work will be completed during the same shift it was removed

operability retests required.

C. opposite train component is operable

Fire Impairments required.

D. opposite train component is operable

operability retests required.



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The plant is in Mode 6 with core alterations in progress

At 0700 on August 9th it was determined that the 7 day channel functional test surveillance on the Source Range Flux Monitors has not been performed since 0700 on August 1st.

Which ONE of the following actions apply? A. Immediately suspend CORE ALTERATIONS or operations that could dilute the RCS

to less than required by Tech Spec 3.9.1. B. Determine the boron concentration of the Reactor Coolant System at least once per

12 hours. C. Perform the channel functional test within the next 18 hours per the allowance of

Tech Spec 4.0.2. D. Invoke Tech Spec 4.0.3 and perform the channel functional test within the next 24

hours.



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A radiological release is in progress following a LOCA outside of Containment

The Emergency Coordinator is evaluating E Plan

Data is now available for a PARs determination

The EC directs you to perform this determination per EP-002-052, Protective Action Guidelines.

The following data is available:

Duration of release is unknown

Wind Directions is 345 º

EAB TEDE

Mr/hr

EAB CDE

Thyroid Mr/hr

2 mile TEDE

Mr/hr

2 mile CDE

Thyroid Mr/hr

5 mile TEDE

Mr/hr

5 mile CDE

Thyroid Mr/hr

1250 3200 750 1900 50 730

Which ONE of the following PAR actions meets the required recommendations of EP-002-052, Protective Action Guidelines? EVACUATE

A. A1, B1, C1, D1 B. A1, B1, C1, D1, D2 C. A1, B1, C1, D1, B2, D2 D. A1, B1, C1, D1, D2, D3, D4



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RAD MONITOR SYS ACTIVITY HI-HI annunciator is in alarm

Plant Stack PIG A and B show rising activity

HVAC Duct PIG D shows rising activity

HVAC Duct PIG A is in alarm

Chemistry Tech reports HIGH airborne activity in the lab following sampling. Based on this information, the CRS should carryout the actions in: A. OP-901-401, High Airborne Activity in Control Room B. OP-901-402, High Airborne Activity in Reactor Auxiliary Building C. OP-901-403, High Airborne Activity in Containment D. OP-901-404, High Airborne Activity in Fuel Handling Building



Page 25 of 25

Question S25 As the Emergency Coordinator, what is the time limit for notification of Operations Hotline Members when plant conditions warrant upgrading from an Unusual Event to an Alert? A. 15 minutes B. 30 minutes C. 45 minutes D. 60 minutes

Waterford Unit 3 - 2009-10 - Final Written Exams. · RO 16 Tech Spec 3.8.2 RO 32 OP-902-009...

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Transcript of Waterford Unit 3 - 2009-10 - Final Written Exams. · RO 16 Tech Spec 3.8.2 RO 32 OP-902-009...